ML20214J611
| ML20214J611 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/08/1986 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8608150095 | |
| Download: ML20214J611 (21) | |
Text
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a.
l Docket Nos.: 50-369 AUG 0 81985 and 50-370 l
LICENSEE:
Duke Power Company FACILITY:
McGuire Nuclear Station, Units 1 and 2
SUBJECT:
SUMMARY
OF JULY 25, 1986, MEETING REGARDING PLUGGING OF FTEAM GENERATOR TUBES WITH CRACKS IN THE TUBESHEET REGION On July 25, 1986, the NRC staff met in Bethesda, Maryland with Duke Power Company (the licensee) and Westinghouse to discuss the licensee's request by letters dated June ?4, July 1 and July 23, 1986, to change steam genar-ator tube plugging criteria in the Technical Specifications. Meeting attendees are listed in Inclosure 1.
The meeting agenda consisted of ten requests for additional information listed in NRC memorandum " Telephone Conversation Regarding Tube Plugging Criteria, McGuire Nuclear Station, Units 1 and 2," dated July 24, 1986.
The licensee stated that the replies would be incorporated into a Westing-house technical report and transmitted to NRC during the week of August 4, 1986.
[Accordingly, the reader is referred to the licensee's letter of August 5,1986, with its attached reports WCAP-11224 (Proprietary) and WCAP-11225 (Non-proprietary), entitled "Tubesheet Region Plugging Criteria for the Duke Power Company McGuire Nuclear Station Units 1 and 2 Steam Generators" for the technical details of this meeting.] is a copy of the viewgraph slides used during the non-proprietary portion of the meeting.
IS Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Enclosures:
As stated i
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Mr. H. B. Tucker Duke Power Company McGuire Nuclear Station cc:
Mr. A. Carr Dr. John M. Barry Duke Power Company Department of Environmental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 Mr. F. J. Twogood County Manager of Meck.lenburg County Power Systems Division 720 East Fourth Street Westinghouse Electric Corp.
Charlotte, North Carolina 28202 P. O. Box 355 Pittsburgh, Pennsylvania 15230 Chairman, North Carolina Utilities Comission Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street Nuclear Production Department Raleigh, North Carolina. 27602 P. O. Box 33189 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief Radiation Protection Branch J. Michael McGarry, III, Esq.
Division of Facility Services Bishop, Liberman, Cook, Purcell Department of Human Resources and Reynolds P.O. Box 12200 1200 Seventeenth Street, N.W.
Raleigh, North Carolina 27605 Washington, D. C.
20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Comission Route 4, Box 529 Hunterville, North Carolina 28078 l
Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 L. L. Williams l
Operating Plants Projects Regional Manager Westinghouse Electric Corporation - R&D 701 P. O. Box 2728 Pittsburgh, Pennsylvania 15230
n-Attendees July 25,1986 Name Organization D. Hood PAD-4/PWR-A/NRR D.A. Lindgreen W NTSD Nuclear Safety G.W. Whitman W NTSD Nuclear Safety J.B. Day Duke Licensing Dan Mayes Duke Maintenance Bob Keating W STD C.Y. Cheng NRC/PWR-B/EB J. Rajan NRC/PWR-B/EB S. Lee NRC/PWR-B/EB E. Sullivan NRC/PWR-A/EB P. Troy SCE8G/Dir. Nuclear Services A.L. Sudduth Duke / Design / Engineering J.G. Connelly SCE&G/Dir. Nuclear Services R. Ballard NRC/PWR-A/EB W
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Viewgraph Slides l
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3 NRC MEETINO PROPOSED STEAM GENERATOR TUBE PLUGGING (F*) CRITERION BETHESDA MARYLAND 7/25/86 ITEM PRESENTER 1.
INTRODUCTION DUKE POWER 2.
RESPONSE TO NRC STAFF TEC5HNICAL DUKE POWER /
QUESTIONS WESTINGHOUSE 3.
SUMMARY
DUKE POWER 4.
ACTIONS t
NRC STAFF l
l
- 1. FLAW SIZING FOR STRESS CORROSION CRACKING o
FLAW SIZING UNCERTAINTY FOR STRESS CORROSION CRACKS IN THE TUBE SHEET BY EXISTING EDDY CURRENT TESTING METHOD IS A GENERIC ISSUE A.
PHASE RELATIONSHIP FOR SIZING ID SIGNALS IS 100% THROUGH WALL OVER 40 DEGREES OF PHASE ANGLE SPREAD B.
TUBESHEET SIGNAL IS DIFFICULT TO MIX OUT DUE TO GEOMETRIC CHANGES WITHIN THE TUBESHEET o
INDUSTRY IMPROVEMENTS HAVE BEEN MADE :
A.
ROTATING PANCAKE COIL PROBE TO CHARICTERIZE DEFECTS l
1.
DETERMINE AXIAL VS. CIRCUMFERENTIAL ORIENTATION 2.
DETERMINE FLAW LENGTH 3.
DETERMINE NUMBER OF DEFECTS B.
PROFILING SOFTWARE TO CHARACTERIZE TUBESHEETS i
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2.
PULLOUT TESTING o
WESTINGHOUSE HAS CONDUCTED CONSERVATIVE PROTOTYPIC TUBE PULLOUT TESTS o
TEST CONDITIONS:
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[
]THERMALRELAXATIONONTHEHARDROLLJOINT (ACHIEVED THROUGH A 4 HOUR SOAK)
PULL TESTS CONDUCTED AT ROOM TEMPERATURE SIMULATING YARIOUS %
WALL THINNING CONDITIONS TESTS WERE CONDUCTED AT POSTULATED FLB PRESSURE
._o, TEST RESULTS l
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HISTORICAL DATA BEING GATHERED FRENCH JAPANESE l
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WESTINGHOUSE STEAM GENERATOR TECHNOLOGY DIVISION
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W E ST INGHOUSE FORM 68047 l
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USE OF COLLAR VERSUS STEAM GENERATOR TUBESHEET O
COLLAR SIZES DETERMINED BASED DN FINITE ELEMENT ANALYSIS WHICH MODELED A SIGNIFICANT PORTION OF THE TUBESHEET o
DIAMETER OF COLLAR DERIVED BASED DN FINITE ELEMENT MODEL RADIAL FLEXIBILITY DETERMINATION WITHIN THE TUBESHEET O
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THERMAL EFFECTS REDUCTION OF CONTACT PRESSURE o
NO SIGNIFICANT YlELDING EXPECTED DURING PLANT HEATUP o
PRELOAD STRESS GAIN DUE TO THERMAL EXPANSION TIGHTENING DURING HEATUP COULD BE REDUCED DURING YIELDING EFFECTIVE ENGAGEMENT LENGTH BASED IS ON PRELOAD STRESS (HARDROLLING IS 100% EFFECTIVE [
] INCHES INTO THE MECHANICAL ROLL) a, n. n 8
1
5.
BORIC ACID EFFECTS ON TUBESHEET AND TUBE PULLOUT FORCE o
THROUGH-WALL CRACK WOULD BE EXPECTED TO RESULT IN NO LEAKAGE o
IF LEAKAGE DOES OCCUR, SMALL VOLUME WOULD BE CONSUMED BY SURFACE REACTIONS NO REPLENISHMENT OF PRIMARY WATER FOR CONTINUED CORROSION o
ANY CORROSION WHICH DOES TAKE PLACE WOULD BE EXPECTED TO INCREASE THE FRICTION COEFFICIENT I.E., NO LUBRICATING EFFECT DUE TO THE PRESENCE OF BORON IS EXPECTED o
WESTINGHOUSE HAS RECOMMENDED CREVICE FLUSHING WITH BORIC ACID i
CONCENTRATIONS l
1 l
r 6.
TUBE DEGRADATION EFFECT ON CONTACT PRESSURE INDICATIONS ARE SHORT, AXIALLY ORIENTED AND LEAK TIGHT o
CRACK INITIATION DOES NOT RESULT IN STRESS RELIEF ISSUE IS NOT TUBE PULLOUT DURING POSTULATED ACCIDENT CONDITION LDADINGS BUT EXPECTED PRIMARY TO SECONDARY LEAKAGE O
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LOWER BOUND TEST DATA IMPACT ON F* DEVELOPMENT o
INCLUDING END EFFECTS, THE REQUIRED HARDROLL ENGAGEMENT LENGTH INCREASES APPROXIMATELY 5%
USING LOWER BOUND DATA FROM THAT REPORTED IN WCAP-10949 o
DUKE POWER CURRENTLY PLANS ON IMPLEMENTING A HARDROLL ENGAGEMENT
- LENGTH, F*, OF 2.0 INCHES
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EFFECT DF HARDROLL DVERROLLS AND UNDERRDLLS o
FOR DVERROLLS F* WILL BE DETERMINED FROM THE SECONDARY FACE OF THE TUBESHEET o
FOR UNDERROLLS F* WILL BE DETERMINED FROM THE ROLL TRANSITION NEAR THE SECONDARY FACE OF THE TUBESHEET 9
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9.
ANALYTICAL PROCEDURES o
STANDARD ANALYSIS EFFECTS INCLUDING THICKNESS EFFECTS UTILIZED:
THICK CYLINDER EQUATIONS FROM ROARK, DEFLECTION FORMULA'S FOR LONG, THIN WALLED CYLINDERICAL SHELLS FROM RDARK PRESSURE EQUATIONS DIFFERENTIATED TO PROVIDE FLEXIBILITIES FOR EASE OF CALCULATION MODIFIED PRESSURE EQUATIONS TO ACCOUNT FOR PLANE STRAIN
=
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SUMMARY
DUKE POWER RESPONSE TO NRC STAFF TECHNICAL QUESTIONS INDICATIONS ARE SHORT, AXIALLY ORIENTED 'AND LEAKTIGHT ISSUE IS NOT TUBE PULLOUT DURING POSTULATED ACCIDENT CONDITION LOADINGS BUT EXPECTED PRIMARY TO SECONDARY LEAKAGE EMPIRICAL TUDE PULL DUT TESTS SUBSTANTIATE PREVIOUS ANALYTICAL RESULTS BORIC ACID EFFECTS ON TUBESHEET AND TUBE PULLOUT FORCE IS EXPECTED TO
~^
BE NEGLIGIBLE a, C.W ENGAGEMENT LENGTH, F*,[NECESSARYTOPRECLUDETUBEPULLDUTIS CALCULATED TO BE [
] INCHES UNDER THE POSTULATED CONDITION OF 360 DEGREE CIRCUMFERENTIAL CRACKING WHICH IS NOT CONSISTENT WITH KNOWN INDICATIONS AS OUTLINED ABOVE
Duke Power Company l
McGuire Unit 1
6/86 RFO Steam Generator inspection STEAM GENERATOR A
B C
U Tubes inspected
- 312F 323F 912P 4558P Row 1 Tubes Plugged 96 96 96 95 Tube Sheet Ind. Plugged 2' O O
2 35 Tube Sheet Ind.
O O
3 136 l
F = Full Length P = Partial Length HTS-1 TSP
l
-s Duke Power Company McGuire Unit 2 8/86 RFO Steam Generator inspection i
B C
D l
Tubes hspecteo 565F 419F 1277P 627P Row 1 Tubes Pluoged 114 114 114 64 Tibe Sheet hi Plugged O
O 2
1 Tube Sheet heg.
79 107 45 53
MEETING
SUMMARY
DISTRIBUTION AUG 0 81936
= - -
liFoc.ketiFihiiM NRC Participants J
NRC PDR C.Y. Cheng L PDR J. Rajan
.NSIC S. Lee PRC System E. Sullivan PWRf4 Reading File R. Ballard DHood M. Duncan OGC J. Partlow E. Jordan B. Grimes ACRS (10)-
OTHERS bec:
Licensee & Service List
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